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Category:Meeting Briefing Package/Handouts
MONTHYEARML24306A0122024-10-29029 October 2024 The Power Journey a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24299A1612024-10-25025 October 2024 Advanced Sensors and Instrumentation Characterizing Nuclear Cybersecurity Using Ai/Ml (Presentation) ML24292A0652024-10-18018 October 2024 Evolving the Legacy of DOE/EH-0545 in the DOE Handbook 1220 ML24292A0612024-10-18018 October 2024 The Power Journey - a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24284A1152024-10-11011 October 2024 S9 Panel ML24274A3202024-10-0404 October 2024 S9P2-Sircar NRC-NEA Harvesting WS-to NEA ML24283A1052024-10-0404 October 2024 S9P1-Tregoning-NRC Presentation on Us Harvesting Activities for Concrete Harvesting Workshop ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24276A0012024-10-0202 October 2024 Regulatory Implications of Advanced Technologies for Component Condition Monitoring in Nuclear Energy Systems ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data ML24274A0422024-10-0101 October 2024 Maritime Perspectives- Presentation for Abs and INL Offshore Nuclear Workshop ML24271A1332024-09-27027 September 2024 Xlpr - Looking to 20 Years of Continuous Development and Applications ML24254A2682024-09-16016 September 2024 Research Information Letter (Ril) 2024-12, Part II on 2023 NRC AMT Workshop ML24172A2962024-06-25025 June 2024 11 - NRC Support to Standards Orgs and Preparations for Future Reactors, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24172A2952024-06-25025 June 2024 10 - Overview of NRC Materials Research Supporting Long-Term Operation, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24162A2772024-06-10010 June 2024 Favpro Release Public Meeting Slides ML24137A0872024-05-14014 May 2024 Regulatory Considerations for Digital Twins for Nuclear Energy Systems - Presentation ML24115A0652024-04-23023 April 2024 Correct-by-Construction Reactor Protection Systems-PowerPoint Presentation ML24075A1902024-03-31031 March 2024 Nondestructive Examination Research at NRC 3-8-24 RIL 2024-01, NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01)2024-03-31031 March 2024 NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01) ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24075A0272024-03-15015 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24016A1762024-01-16016 January 2024 Integrated Safety, Security, and Safeguards Ffr Research Project ML23342A1642023-12-0808 December 2023 Networking and Information Technology Research and Development Program Software Productivity Sustainability and Quality (Spsq) NRC - Sushil Birla December 14, 2023 ML23292A0922023-10-30030 October 2023 Advanced Sensor and Instrumentation - NRC Research Status Update ML23298A0312023-10-26026 October 2023 Advanced Fuel Cycle Storage and Transportation Research ML23324A2702023-10-24024 October 2023 Session - Key Takeaways ML23324A2322023-10-24024 October 2023 S0P1 - Focht - 2023 NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications -Workshop Overview- ML23324A2332023-10-24024 October 2023 S0P2 - Focht - NRC AMT Activities Overview v2.0 ML23275A0022023-10-0505 October 2023 Domain Modeling & Domain Engineering an Enabler for Correct-by-Construction Design ML23272A0332023-09-29029 September 2023 Identifying Hazards in a System Design ML23264A0212023-09-28028 September 2023 Addressing Hazards from Common Causes in Engineering Di&C Systems Without Diverse Designs - State-of-the-Art ML23264A0252023-09-20020 September 2023 September 20, 2023 - Dent Presentation - John Mckirgan - Research Activities in Support of Digital Engineering in Nuclear Technology ML23256A0102023-09-18018 September 2023 State-of-the-art Approaches to Reduce the Potential for CCF in I&C Systems Conditions to Avoid the Need for Diversity in Design ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (RIPB) Standards ML23251A0582023-09-13013 September 2023 Session 2 - International Initiatives on Codes and Standards ML23251A0572023-09-13013 September 2023 Session 1 - Importance of Standards, Opportunities for Participation and Collaboration ML23242A1182023-09-0707 September 2023 Research Challenges and Opportunities in the Safety Assurance of Nuclear Reactors ML23248A2142023-09-0606 September 2023 Reactor Safety: Regulatory Objectives & Framework ML23242A0032023-08-31031 August 2023 Reactor Protection System for the Virtual Ford Nuclear Reactor Designed-in Assurance ML23194A1872023-07-20020 July 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23152A1802023-06-14014 June 2023 13 - NRC - Materials Harvesting Activities ML23152A1702023-06-14014 June 2023 14 - NRC - PWSCC Initiation ML23130A0042023-05-11011 May 2023 Challenges in Assuring Safety of Nuclear Reactor Protection Systems - One Perspective ML23067A3402023-03-0707 March 2023 Presentation, N-853-1 Proposed Revision Technical Exchange with Electric Power Research Institute Welding and Repair Technology ML22322A0432022-11-18018 November 2022 Regulatory Research on the Aging Management of Structures, Systems and Components in Nuclear Power Plants for Second License Renewal, Presentation Slides 2024-09-27
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24313A1662024-11-13013 November 2024 NRC Metals Research Supporting Long-Term Operation Update for Lwrs Stakeholders Meeting November 13, 2024 ML24306A0122024-10-29029 October 2024 The Power Journey a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24299A1612024-10-25025 October 2024 Advanced Sensors and Instrumentation Characterizing Nuclear Cybersecurity Using Ai/Ml (Presentation) ML24284A1152024-10-11011 October 2024 S9 Panel ML24283A1052024-10-0404 October 2024 S9P1-Tregoning-NRC Presentation on Us Harvesting Activities for Concrete Harvesting Workshop ML24274A3202024-10-0404 October 2024 S9P2-Sircar NRC-NEA Harvesting WS-to NEA ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24276A0012024-10-0202 October 2024 Regulatory Implications of Advanced Technologies for Component Condition Monitoring in Nuclear Energy Systems ML24274A0422024-10-0101 October 2024 Maritime Perspectives- Presentation for Abs and INL Offshore Nuclear Workshop ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24271A1332024-09-27027 September 2024 Xlpr - Looking to 20 Years of Continuous Development and Applications ML24254A2682024-09-16016 September 2024 Research Information Letter (Ril) 2024-12, Part II on 2023 NRC AMT Workshop ML24172A2962024-06-25025 June 2024 11 - NRC Support to Standards Orgs and Preparations for Future Reactors, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24172A2952024-06-25025 June 2024 10 - Overview of NRC Materials Research Supporting Long-Term Operation, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24162A2772024-06-10010 June 2024 Favpro Release Public Meeting Slides ML24137A0872024-05-14014 May 2024 Regulatory Considerations for Digital Twins for Nuclear Energy Systems - Presentation ML24115A0652024-04-23023 April 2024 Correct-by-Construction Reactor Protection Systems-PowerPoint Presentation RIL 2024-01, NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01)2024-03-31031 March 2024 NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01) ML24075A1902024-03-31031 March 2024 Nondestructive Examination Research at NRC 3-8-24 ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24081A1102024-03-18018 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems - Final ML24075A0272024-03-15015 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24016A1762024-01-16016 January 2024 Integrated Safety, Security, and Safeguards Ffr Research Project ML23342A1642023-12-0808 December 2023 Networking and Information Technology Research and Development Program Software Productivity Sustainability and Quality (Spsq) NRC - Sushil Birla December 14, 2023 ML23292A0922023-10-30030 October 2023 Advanced Sensor and Instrumentation - NRC Research Status Update ML23298A0312023-10-26026 October 2023 Advanced Fuel Cycle Storage and Transportation Research ML23324A2702023-10-24024 October 2023 Session - Key Takeaways ML23324A2322023-10-24024 October 2023 S0P1 - Focht - 2023 NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications -Workshop Overview- ML23324A2332023-10-24024 October 2023 S0P2 - Focht - NRC AMT Activities Overview v2.0 ML23275A0022023-10-0505 October 2023 Domain Modeling & Domain Engineering an Enabler for Correct-by-Construction Design ML23272A0332023-09-29029 September 2023 Identifying Hazards in a System Design ML23264A0212023-09-28028 September 2023 Addressing Hazards from Common Causes in Engineering Di&C Systems Without Diverse Designs - State-of-the-Art ML23264A0252023-09-20020 September 2023 September 20, 2023 - Dent Presentation - John Mckirgan - Research Activities in Support of Digital Engineering in Nuclear Technology ML23262A9842023-09-19019 September 2023 MPA Seminar 2023 - Evaluation of Molten Salt Compatibility with Structural Alloys ML23256A0102023-09-18018 September 2023 State-of-the-art Approaches to Reduce the Potential for CCF in I&C Systems Conditions to Avoid the Need for Diversity in Design ML23251A0582023-09-13013 September 2023 Session 2 - International Initiatives on Codes and Standards ML23251A0572023-09-13013 September 2023 Session 1 - Importance of Standards, Opportunities for Participation and Collaboration ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (RIPB) Standards ML23242A1182023-09-0707 September 2023 Research Challenges and Opportunities in the Safety Assurance of Nuclear Reactors ML23248A2142023-09-0606 September 2023 Reactor Safety: Regulatory Objectives & Framework ML23242A0032023-08-31031 August 2023 Reactor Protection System for the Virtual Ford Nuclear Reactor Designed-in Assurance ML23206A1592023-07-27027 July 2023 Identifying Hazards from Engineering Digital I&C Systems: State of the Art ML23194A1872023-07-20020 July 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23187A4862023-07-0606 July 2023 Nrc’S Digital I&C Research for Application in Nuclear Power Plants – Status Update Presentation at Npic&Hmit 2023 ML23187A4762023-07-0606 July 2023 Advanced Sensors and Instrumentation –Nrc Research Status Update Presentation at Npic&Hmit 2023 ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23152A1772023-06-15015 June 2023 28 - NRC - Fatigue Data Sharing 2024-09-27
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Text
Leak-Before-Break Studies NRC Phase 1 LBB Report/ Plans for LBB Phase 2 and EPRI Report August 18, 2021 1
Introduction 2
- Application of xLPR to a real-life problem: Impact of primary water stress-corrosion cracking (PWSCC) on a Reactor Vessel Outlet Nozzle (RVON) for a Westinghouse 4-loop Nuclear Power Plant
- Largest number of same weld type with Alloy 82/182 within leak-before-break (LBB)-approved line segments in the U.S. nuclear fleet
- Coordinated effort by NRC/RES and EPRI via a memorandum of understanding, with the following goals:
1.
Develop a defensible strategy of xLPR use for risk-informed decision making 2.
Initiate the first phase of a system-level analysis considering a loop or a whole unit 3.
Test different Quantities of Interest (QoIs) as criteria for decision-making
- Program to be followed by a second phase considering other weld locations and combination of results at the system level
Problem considered 3
- Reactor Vessel Outlet Nozzle (RVON) for a generic Westinghouse 4-loop pressurized-water reactor
- 34 inches diameter (0.869 m)
- 2.6 inches thickness (0.0663 m)
- Temperature : 320.5°C
- Pressure 15.41 MPa
- Focus on circumferential cracks (axial cracks considered in sensitivity run)
- Simulation time : 80 years (timestep : 1 month)
- Large number of uncertain inputs (e.g.,
welding residual stresses (WRS), crack initiation parameters, crack growth parameters)
Quantities of Interest 4
- Probability of rupture with leak rate detection
- Probability of Leak Rate Jump: going from less than 10 gpm to more than 50 gpm in one timestep
- Probabilistic LBB ratio (critical crack size over detectable leakage crack size)
- Similar to the deterministic ratio in NRC Standard Review Plan Section 3.6.3
- Estimated for each realization leading to a distribution of the LBB ratio
- Distribution of time from detectable through wall crack to rupture Outputs in blue are directly estimated in xLPR - other outcomes need postprocessing but can be done easily in Excel
Probabilistic Approach 5
- Considered acceptance threshold is 10-6 occurrence per reactor year.
- Equivalent to probability of occurrence of 8 x 10-5 over 80 years
- Sample size considered between 70,000 and 100,000 should lead to respectively 5 to 8 events on average, if the probability is higher than the threshold
- Analysis conditional on having a crack at time 0 use sample size of 5,000 since probability of having crack over 80 years is in the 10-3 range
- Large amount of data saved, so a single probabilistic run was not practical
- 7 replicates of 10,000 to 15,000 sample size, each with different random seeds, were run and combined
- Crack leak rate, inner length, outer length, and critical ratio extracted to estimate the composite QoIs
Reference results (1/2) 6
- Probability of leak rate jump and rupture with leak rate detection too low to occur over 100,000 realizations
- Good on a regulatory standpoint since it shows the risk is below the acceptable range. Not ideal on a scientific standpoint as there is no quantification of the risk
- Rather, alternate QoIs are presented (P(1st crack),
P(1st leak) and P(rupture) without inspection or leak rate detection)
Reference results (2/2) 7 Composite QoIs give results for different criteria (for instance 1 gpm and 10 gpm leak rate detection limits)
Results are conditional on having pipe rupture and do not reflect this probability 10 gpm 1 gpm LBB ratio Time between detectable leak rate and rupture 10 gpm 1 gpm
Sensitivity Case: Impact of WRS Profile (1/2) 8
- New WRS mean profile with similar uncertainty applied
- Larger mean at insider diameter leads to higher probability of 1st crack
- Lower minimum reduces probabilities of 1st leak and rupture relative to the reference value Still, no ruptures with leak rate detection or leak rate jump events
Sensitivity Case: Impact of WRS Profile (2/2) 9
- Stronger impact on LBB ratio and LBB time lapse than for the reference case
- Use of multiple metrics gives more insights on scenario differences and increases confidence in the results
Sensitivity Case: Impact of Temperature 10
- Change in operating temperature (deterministic value) from 320.8°C to 330°C
- Considered large change since the same temperature is applied through the whole 80-year simulation time
- Temperature affects initiation and growth, thus impact in all three metrics presented Still, no ruptures with leak rate detection or leak rate jump events
Conclusions and Perspectives 11
- This study helped identify bugs and enhancements for xLPR (they will be fixed in Version 2.2) but overall, the code is ready to be used for regulatory decisionmaking
- Beyond the already available outputs, composite QoIs can be defined and calculated in post-processing without too much effort
- This study helped identify advantages and drawbacks for each QoI considered and showed the benefit of using multiple metrics
- This first analysis serves as a good basis to extend the process to other weld types (pressurizer surge line, reactor coolant pump ) and estimate risk at the system level